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AmMizuyama, Kazuhito; Iwamoto, Nobuyuki; Iwamoto, Osamu
no journal, ,
The accuracy of nuclear data for the minor actinides (MAs) included in the high level radioactive wastes which have the long term radiotoxicity is required to be improved for the environmental load reduction technique. However, there is large discrepancy among the previous measurements for MAs. The Cadmium(Cd)-ratio method is the analysis method to deduce the 
and the s-factor by using the Cd-ratio given by the reaction rates without(with) the Cd-filter. The s-factor is defined by the normalized resonance integral by after subtracting 1/v component. Since there are lower resonances than the cut-off energy in Am, it is necessary to correct the effect of them in order to deduce the accurately. In this study, we evaluated the effect of the lower resonances than the cut-off energy as the correction of s-factor from the JENDL-4.0, and corrected the existing the data. As a result, the consistency among the measurements was improved.
-ray irradiationMotooka, Takafumi; Ueno, Fumiyoshi
no journal, ,
Crevice corrosion of a couple of zirconium and SUS304L were investigated in dilute artificial seawater at ambient temperature under Co-60 -ray irradiation by electrochemical technique to clarify the occurrence criteria of crevice corrosion. Under simulated an aqueous circumstance in spent fuel pools in Fukushima Daiichi nuclear plant, crevice corrosion potential was greater than spontaneous potential. This result suggests that crevice corrosion little occurs in the dilute chloride solution simulating the spent fuel pool circumstance.
Hanari, Toshihide; Yamada, Tomonori; Matsunaga, Yukihiro; Nguyen, P. L.; Nakamura, Masaki; Muramatsu, Toshiharu
no journal, ,
no abstracts in English
-ray induced nuclear dataIwamoto, Nobuyuki
no journal, ,
Photonuclear data are required in the field for, e.g., shielding design of high-energy electron linear accelerator, high-energy -ray therapy, and non-destructive assay. This work aims at developing photonuclear reaction data file with a wide range of nuclides for more extensive use. In order to perform evaluation in the -ray energy up to 140 MeV, nuclear reaction model calculation code CCONE was used. The modified Lorentzian model was applied to describe giant dipole resonance. The resonance parameters were fixed by reproducing photoabsorption data. The quasi-deuteron model was also taken into account in this present code. The nuclear level density was adopted from Gilbert-Cameron formalism with Mengoni-Nakajima Fermi-gas model. The evaluated results were compared with the measured data, JENDL/PD-2004 and KAERI data and showed good agreements with the measured data. These evaluated data are planned to be included into the next photonuclear data file.
Kunieda, Satoshi; Iwamoto, Osamu; Iwamoto, Nobuyuki; Minato, Futoshi; Okamoto, Tsutomu; Sato, Tatsuhiko; Nakashima, Hiroshi; Iwamoto, Yosuke; Iwamoto, Hiroki; Kitatani, Fumito; et al.
no journal, ,
Neutron- and proton-induced evaluated nuclear data are required in a wide energy range for the design of accelerator applications. New evaluations are performed with recent progresses in the optical and pre-equilibrium model calculations. We also evaluated cross-sections for p + 
Li and p + 
Be which are highly requested from medical field. Our present high-energy nuclear data library, JENDL-4.0/HE, includes cross-sections for 132 nuclei up to 200 MeV. In this talk, we present the evaluation methods, evaluated double-differential cross-sections and results of benchmark calculations.
Kimura, Atsushi; Nakamura, Shoji; Terada, Kazushi; Nakao, Taro; Toh, Yosuke; Harada, Hideo; Igashira, Masayuki*; Katabuchi, Tatsuya*; Mizumoto, Motoharu*; Takamiya, Koichi*; et al.
no journal, ,
no abstracts in English
Yamano, Hidemasa; Nishino, Hiroyuki; Kurisaka, Kenichi; Okano, Yasushi; Sakai, Takaaki; Yamamoto, Takahiro*; Ishizuka, Yoshihiro*; Furukawa, Ryuta*; Geshi, Nobuo*; Nanayama, Futoshi*; et al.
no journal, ,
PRA and margin assessment methodologies are being developed for sodium-cooled fast reactors against representative external hazards. This report describes the overview of Third-year (JPY2014) updates and the development of the sequence assessment methodology against volcanic eruption hazard.
Iwamoto, Hiroki; Nishihara, Kenji; Iwamoto, Yosuke; Hashimoto, Shintaro; Sato, Tatsuhiko
no journal, ,
no abstracts in English
Nozawa, Takashi; Park, J.-S.*; Nakazato, Naofumi*; Ozawa, Kazumi; Tanigawa, Hiroyasu
no journal, ,
Silicon carbide is a candidate nuclear materials because of low-activation and superior irradiation resistance as well as perceived various characteristics inherently featured as prominent engineering ceramics and a continuous fiber reinforced composite has generally been developed due to brittleness of SiC itself. Of many material parameters for design, validation of high temperature durability at approximately 1000
C is essential. Understanding of anisotropy of woven composite strength is also very important. Besides, developing comprehensive model to predict composite strength by various modes with a limited data set. This study aims to summarize the features of fracture behavior by tensile, compressive and shear at elevated temperatures. With consideration of the prediction model, we finally obtain the high temperature strength anisotropy map.
Nakatsuka, Yoshiaki; Zaima, Naoki; Nakashima, Shinichi; Fujiki, Naoki*; Suwaki, Takuro*; Kureta, Masatoshi; Ozu, Akira; Komeda, Masao
no journal, ,
The historical procedures and target of active neutron measurements devices will be reported beside requirements of SG/MA tools. Also introduced the principles of FNDI methods and its applicability.
Fujiki, Naoki*; Nakatsuka, Yoshiaki; Zaima, Naoki; Nakashima, Shinichi; Suwaki, Takuro*; Kureta, Masatoshi; Ozu, Akira; Komeda, Masao
no journal, ,
The performances of methodological characteristics, operation stability and radiation control of active neutron measurements devices will be reported.
Yokoyama, Kenji; Ishikawa, Makoto; Numata, Kazuyuki; Usami, Shin; Takeda, Toshikazu*
no journal, ,
no abstracts in English
Suwaki, Takuro*; Zaima, Naoki; Nakatsuka, Yoshiaki; Fujiki, Naoki*; Nakashima, Shinichi; Kureta, Masatoshi; Ozu, Akira; Komeda, Masao
no journal, ,
The mockup tests used standard uranium source and simulated matrices have been successfully performed. The well performances of this device are introduced.
Zaima, Naoki; Nakatsuka, Yoshiaki; Nakashima, Shinichi; Fujiki, Naoki*; Suwaki, Takuro*; Kureta, Masatoshi; Ozu, Akira; Komeda, Masao
no journal, ,
The trials for measuring actual waste drums have been performed, and validated good applicability active neutron measurements device on site.
Edao, Yuki; Iwai, Yasunori; Hayashi, Takumi
no journal, ,
no abstracts in English
Iwai, Yasunori; Kubo, Hitoshi*; Oshima, Yusuke*
no journal, ,
Water detritiation technology for the Combined Electrolysis Catalytic Exchange (CECE) process has been developed over the years in Japan Atomic Energy Agency (JAEA) for the Japanese DEMO fusion reactor. The research interest is in (1) durability of a commercial polymeric ion exchange membrane for tritiated water electrolyzer and improvement of a membrane for the enhance in durability, in (2) sorption behavior of tritiated water in elastomers for promising seal materials of the electrolyzer, and in (3) development of hydrophobic catalyst for the reaction of hydrogen isotope exchange between hydrogen and water vapor in the Liquid Phase Chemical Exchange (LPCE) column. For the durability of ion exchange membrane, durability of Nafion ion exchange membrane immersed into 1.38
10 TBq/kg of highly concentrated tritiated water has been demonstrated at room temperature for up to 3 years as a Broader Approach activity. The changes in mechanical strength and ion exchange capacity after immersing in tritiated water are well consistent with those irradiated to an equivalent dose with rays or electron beams. As for the sorption behavior of tritiated water in elastomers, change in sorption behavior of water in elastomers irradiated up to 1500 kGy has been evaluated for more than 8 years. For the hydrophobic catalyst, the Japan Atomic Energy Agency and Tanaka Kikinzoku Kogyo K.K developed a new method of manufacturing catalysts involving hydrophobic processing with an inorganic substance base. The catalyst created with this method has achieved the highest exchange efficiency, equivalent to 1.3 times the previously most powerful efficiency.
Sugimoto, Masayoshi; Wakai, Eiichi; Kanemura, Takuji; Kikuchi, Takayuki; Ida, Mizuho*; Watanabe, Kazuyoshi*; Niitsuma, Shigeto*; Yamamoto, Michiyoshi*; Yutani, Toshiaki*; Hirano, Michiko*
no journal, ,
The International Fusion Materials Irradiation Facility - Engineering Validation and Engineering Design Activities (IFMIF/EVEDA) is a EU an Japan collaborative project under the framework of the Broader Approach activities for fusion energy development and, after the Intermediate Engineering Design Report has been completed in 2013, the validation test tasks have been conducted up to 2015. About the tasks in charge of Japan were completed in March and now we continue the evaluation of the testing results and examine how to reflect them to updated engineering design. In this report, we present the technical validity of the design based on the results of various validation tests and summarize the issues to be solved in future.
Sakamoto, Atsushi; Sano, Yuichi; Takeuchi, Masayuki; Ito, Kazuyuki*; Sekita, Satoshi*; Sakamoto, Yukio*; Akutsu, Koichi*
no journal, ,
no abstracts in English
Saito, Kimiaki
no journal, ,
no abstracts in English
Okano, Yasushi; Yamano, Hidemasa
no journal, ,
As a part of the development of forest fire hazard assessment method and event sequence analyses method for a sodium-cooled fast reactor, this paper describes the analysis of hazard curves of fireline intensity and reaction intensity as heat and flame effects of a forest fire by a logic tree improvements, response surface evaluations, and Monte Carlo simulations applying importance sampling.